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首页> 外文期刊>Journal of Heat Transfer >Pressure Drop and Void Fraction in Steam-Water Two-Phase Flow at High Pressure
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Pressure Drop and Void Fraction in Steam-Water Two-Phase Flow at High Pressure

机译：高压蒸汽-水两相流中的压降和空隙率

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摘要

For a steam generator (SG) in a commercialized sodium-cooled fast breeder reactor (FBR), flow instability in the water side is one of the most important items needing research. As the first step of this research, thermal-hydraulic experiments using water as the test fluid were performed under high pressure conditions at the Japan Atomic Energy Agency (JAEA) by using a circular tube. Void fraction, pressure drop, and heat transfer coefficient data were obtained under 15,17, and 18 MPa. This paper discusses the steam-water pressure drop and void-fraction. Using the obtained data, we evaluated existing correlations for void fraction and two-phase flow multipliers under high pressure. As a result, the drift flux model implemented in the TRAC-BF1 code was confirmed to suitably predict the void fraction well under the present high pressure conditions. For the two-phase flow multiplier, the Chisholm correlation and the homogeneous model were confirmed to be the best under the present high-pressure conditions.
机译：对于商业化钠冷快中子增殖堆（FBR）中的蒸汽发生器（SG），水侧的流动不稳定性是需要研究的最重要的项目之一。作为这项研究的第一步，在高压条件下，日本原子能机构（JAEA）使用圆管在水中进行了以水为测试液的热工实验。在15、17和18 MPa下获得空隙率，压降和传热系数数据。本文讨论了蒸汽-水压降和空隙率。使用获得的数据，我们评估了高压下空隙率和两相流乘数的现有相关性。结果，证实了用TRAC-BF1代码实现的漂移通量模型可以很好地预测当前高压条件下的空隙率。对于两相流乘数，在当前的高压条件下，Chisholm相关性和均质模型被确认为最佳。

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